ICMST-Tohoku 2018
Oct. 23 - 26, 2018
Sendai, Japan
ICMST-Shenzhen 2016
Nov 1 - 4, 2016
Shenzhen, China
ICMST-Kobe 2014
Nov 2(Sun) - 5(Wed), 2014
Kobe, Japan
Nuclear Regulation Authority Outline of the New Safety Standards for Light Water Reactors for Electric Power Generation
For Public Comment
Outline of New Safety Standard (Design Basis)
For Public Comment
New Safety Standards (SA) Outline (Draft)
For Public Comment
Outline of New Safety Standard(Earthquake and Tsunami)(DRAFT)

Vol.10 No.2(Aug)
Vol.10 No.1(May)
Vol.9 No.4(Feb)
Vol.9 No.3(Nov)

< Other Issues


Occasional Topics
OTjapan Measures for Tsunami Striking Nuclear Power Station in Japan
Special Article: The Great Tohoku Earthquake (1)
OTjapan The Tragedy of “To Be” Principle in the Japanese Nuclear Industry
EJAMOT_CN3_Figure1_The_outside_view_of_CEFR OTChinaPlanning and Consideration on SFR R&D Activities in China
< All Occasional Topics

Featured Articles
EJAM7-3NT72 A New Mechanical Condition-based Maintenance Technology Using Instrumented Indentation Technique
EJAM7-3NT73 Survey robots for Fukushima Daiichi Nuclear Power Plant

(in English)


Vol.6 No.1 previous AA 74-SP11 (75-76)-Errata NT 63 -64

Academic Articles
Regular Paper Vol.6No.1 (2014) p.24 - p.32

Effect of Thermo-Mechanical Loading Histories on Fatigue Crack Growth Behavior and the Threshold
in SUS 316 and SCM 440 Steels
-For prevention of high cycle thermal fatigue failures-

Masakazu OKAZAKI1, Milton MUZVIDZIWA1, Akira IWASAKI1 and Naoto KASAHARA2
1Nagaoka University of Technology, Nagaoka, Niigata, 940-2188, JAPAN
2The University of Tokyo, Hongo, Tokyo, JAPAN
High cycle thermal fatigue failure of pipes induced by fluid temperature change is one of the interdisciplinary issues to be concerned for long term structural reliability of high temperature components in energy systems. In order to explore advanced life assessment methods to prevent the failure, fatigue crack propagation tests were carried out in a low alloy steel and an austenitic stainless steel under typical thermal and thermo-mechanical histories. Special attention was paid to both the effect of thermo-mechanical loading history on the fatigue crack threshold, as well as to the applicability of continuum fracture mechanics treatment to small or short cracks. It was shown experimentally that the crack-based remaining fatigue life evaluation provided more reasonable assessment than the traditional method based on the semi-empirical law in terms of "usage factor" for high cycle thermal fatigue failure that is employed in JSME Standard, S017. The crack propagation analysis based on continuum fracture mechanics was almost successfully applied to the small fatigue cracks of which size was comparable to a few times of material grain size. It was also shown the thermo-mechanical histories introduced unique effects to the prior fatigue crack wake, resulting in occasional change in the fatigue crack threshold.

High cycle thermal fatigue failure, Thermo-mechanical loading history, Small crack, Threshold, Crack wake, Repair, High-cycle and low-cycle fatigue interaction, SUS316, SCM440
Full Paper: PDF EJAM Vol.6No.1 pp.24-32 "Effect of Thermo-Mechanical Loading Histories on Fatigue Crack Growth Behavior and the Threshold in SUS 316 and SCM 440 Steels -For prevention of high cycle thermal fatigue failures-"

Article Information
Article history:
Received 19 December 2013
Accepted 28 April 2014